Abstract
Crack growth rate testing was performed on CT specimens with doses in the range ~10 – 47.5 dpa. Two specimens of Type 304L (same heat) were tested in BWR and PWR environments with the objective to compare the CGR behavior of fast reactor irradiation with BWR irradiation. Three specimens of heats tested previously, but at other doses, were tested for assessment of dose and K on IASCC. One specimen of Type 304L was tested in BWR NWC and HWC at two different K levels, while two specimens of cold worked Type 316 were tested at various K levels and temperatures in PWR primary water. To assess the effect of temperature on IASCC, two specimens were tested in either BWR NWC and HWC or PWR primary water at different temperatures. The paper will discuss the effects of fast reactor versus light water reactor irradiation, K, ECP, dose and temperature on the CGR.
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© 2011 TMS (The Minerals, Metals & Materials Society)
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Jenssen, A., Stjärnsäter, J., Pathania, R. (2011). Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments. In: Busby, J.T., Ilevbare, G., Andresen, P.L. (eds) Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer, Cham. https://doi.org/10.1007/978-3-319-48760-1_75
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DOI: https://doi.org/10.1007/978-3-319-48760-1_75
Publisher Name: Springer, Cham
Online ISBN: 978-3-319-48760-1
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